Engineering critical assessment of RPV with nozzle corner cracks under pressurized thermal shocks |
Li, Yuebing
(State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment, China Nuclear Power Engineering Co., Ltd)
Jin, Ting (State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment, China Nuclear Power Engineering Co., Ltd) Wang, Zihang (Institute of Process Equipment and Control Engineering, Zhejiang University of Technology) Wang, Dasheng (State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment, China Nuclear Power Engineering Co., Ltd) |
1 | S.N. Atluri, K. Kathiresan, Influence of flaw shapes on stress intensity factors for pressure vessel surface flaws and nozzle corner cracks, J. Pressure Vessel Technol. 102 (1980) 278-286. DOI |
2 | S. Chapuliot, S. Marie, Elastic-plastic Fracture Mechanics Assessment of nozzle corners submitted to thermal shock loading, Int. J. Pres. Ves. Pip. 147 (2016) 55-63. DOI |
3 | U.T. Murtaza, M.J. Hyder, Stress intensity factors of corner cracks at set-in nozzle-cylinder intersection of a PWR reactor pressure vessel, J. Braz. Soc. Mech. Sci. Eng. 39 (2017) 601-611. DOI |
4 | U.T. Murtaza, M.J. Hyder, Fracture analysis of the set-in nozzle of a PWR reactor pressure vessel - Part 1: determination of critical crack, Eng. Fract. Mech. 192 (2018) 343-361. DOI |
5 | U.T. Murtaza, M.J. Hyder, The effects of thermal stresses on the elliptical surface cracks in PWR reactor pressure vessel, Theor. Appl. Fract. Mech. 75 (2015) 124-136. DOI |
6 | R. Liu, M. Huang, Y. Peng, et al., Analysis for crack growth regularities in the nozzle-cylinder intersection area of reactor pressure vessel, Ann. Nucl. Energy 112 (2018) 779-793. DOI |
7 | H.W. Chou, Y.Y. Shen, C.C. Huang, Development of pressure-temperature operation limits for a PWR vessel considering beltline shell and extended beltline nozzles, Int. J. Pres. Ves. Pip. (2019) online. |
8 | F. Hirokawa, M. Hayashi, M. Masuda, et al., Defect tolerance assessment for abwr nozzle crotch corner, in: Proceedings of the ASME 2016 Pressure Vessels and Piping Conference, Vancouver, British Columbia, Canada, 2016. |
9 | D. Moinereau, G. Bezdikian, C. Faidy, Methodology for the pressurized thermal shock evaluation: recent improvements in French RPV PTS assessment, Int. J. Pres. Ves. Pip. 78 (2001) 69-83. DOI |
10 | G. Qian, M. Niffenegger, Deterministic and probabilistic analysis of a reactor pressure vessel subjected to pressurized thermal shocks, Nucl. Eng. Des. 273 (2014) 381-395. DOI |
11 | Guian Qian, Y. Cao, M. Niffenegger, et al., Comparison of constraint analyses with global and local approaches under uniaxial and biaxial loadings, Eur. J. Mech. Solid. 69 (2018) 135-146. DOI |
12 | X. Sun, J. Yao, G. Chai, Thickness effects of base wall and inlet pipe on the structural integrity of reactor pressure vessels considering ductile-to-brittle transition, Eng. Fail. Anal. 105 (2019) 1032-1044. DOI |
13 | D. Siegele, L. Hodulak, I. Varfolomeyev, et al., Failure assessment of RPV nozzle under loss of coolant accident, Nucl. Eng. Des. 193 (1999) 265-272. DOI |
14 | T. Jin, Z. Wang, Q. Wang, et al., Weibull stress analysis for the corner crack in reactor pressure vessel nozzle, Adv. Mech. Eng. 11 (2019), 1687814019893567. |
15 | X. Sun, G. Chai, Y. Bao, Elastic and elastoplastic fracture analysis of a reactor pressure vessel under pressurized thermal shock loading, Eur. J. Mech. Solid. 66 (2017) 69-78. DOI |
16 | C.W. Smith, W.H. Peters, W.T. Hardrath, et al., Stress Intensity Distributions in Nozzle Corner Cracks of Complex Geometry, 1979. |
17 | ASME, ASME Boiler and Pressure Vessel Code, Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, App. A, 2010. |
18 | RCC-MR, Construction and Operating Supervision of the Equipment for Electro-Nuclear Boilers (AFCEN), French Association for Design, Construction and In-Service Inspection Rules for Nuclear Island Components, 2007. Paris. |
19 | British Energy, R6-Assessment of the integrity of structures containing defects, ReVision 4 (2010). |
20 | M. Chen, G. Qian, J. Shi, et al., Application of the French codes to the pressurized thermal shocks assessment, Nucl. Eng. Technol. 48 (2016) 1423-1432. DOI |
21 | M. Chen, W. Yu, G. Qian, et al., Crack initiation, arrest and tearing assessments of a RPV subjected to PTS events, Ann. Nucl. Energy 116 (2018) 143-151. DOI |
22 | G. Chai, Q. Hong, Approximate stress intensity factor solutions for nozzle corner cracks, Int. J. Pres. Ves. Pip. 42 (1990) 75-96. DOI |
23 | J.L. Mclean, L.M. Cohen, P.M. Besuner, Effects of location, thermal stress and residual stress on corner cracks in nozzles with cladding, Int. J. Pres. Ves. Pip. 7 (1979) 245-274. DOI |
24 | S.N. Atluri, K. Kathiresan, Stress intensity factor solutions for arbitrarily shaped surface flaws in reactor pressure vessel nozzle corners, Int. J. Pres. Ves. Pip. 8 (1980) 313-322. DOI |
25 | RCC-M, Design and Construction for Mechanical Components of PWR Nuclear Island, Sec. I. Subsec. Z. Annex Z G, Fast Fracture Resistance, French Association for Design, Construction and In-Service Inspection Rules for Nuclear Island Components, 2010. Paris. |
26 | V. Chaudhry, A. Kumar, S.M. Ingole, et al., Thermo-mechanical transient analysis of reactor pressure vessel, Process Eng. 86 (2014) 809-817. |
27 | G. Chai, Q. Hong, Stress intensity factors of nozzle corner cracks, Eng. Fract. Mech. 38 (1991) 27-35. DOI |
28 | S. Chapuliot, Stress intensity factor calculation in sharp and beveled edge nozzle corners, Int. J. Pres. Ves. Pip. 141 (2016) 11-18. DOI |
29 | American Petroleum Institute, API 579-1/ASME FFS-1, Fitness-for-Service, 2007. |
30 | A. Robertson, H. Li, D. Mackenzie, Plastic collapse of pipe bends under combined internal pressure and in-plane bending, Int. J. Pres. Ves. Pip. 82 (2005) 407-416. DOI |
31 | A. Prakash, H.K. Raval, A. Gandhi, et al., Plastic limit load analysis of cylindrical pressure vessels with different nozzle inclination, J. Inst. Eng.: Series C 97 (2016) 163-174. DOI |
32 | S. Yin, G.L. Stevens, B.R. Bass, Fracture analysis for reactor pressure vessel nozzle corner cracks, in: 22nd Conference on Structural Mechanics in Reactor Technology, San Francisco, California, USA, 2013. |
33 | S.Y. Park, J.W. Kim, T.W. Kim, et al., P-T limit curve of reactor pressure vessel with nozzle corner crack, in: The 21st International Conference on Structural Mechanics in Reactor Technology. New Delhi, India, 2011. |
34 | S. Yin, B.R. Bass, G.L. Stevens, Stress and fracture mechanics analyses of boiling water reactor and pressurized water reactor pressure vessel nozzles, in: Proceedings of the ASME 2011 Pressure Vessels & Piping Division Conference. Baltimore, Maryland, USA, 2011. |